A5013527775- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Ion-surface interactions and analysis
- Advanced materials and composites
- Metal and Thin Film Mechanics
- X-ray Spectroscopy and Fluorescence Analysis
- Particle accelerators and beam dynamics
- Electron and X-Ray Spectroscopy Techniques
- Superconducting Materials and Applications
- Semiconductor materials and devices
- Nuclear materials and radiation effects
- ZnO doping and properties
- Robotics and Sensor-Based Localization
- Soft Robotics and Applications
- Integrated Circuits and Semiconductor Failure Analysis
- Cryptographic Implementations and Security
- Radiation Effects in Electronics
- Metallurgical Processes and Thermodynamics
- Augmented Reality Applications
- High-Temperature Coating Behaviors
- Semiconductor materials and interfaces
- High Entropy Alloys Studies
University of Lisbon
2016-2025
Culham Science Centre
2016-2024
Culham Centre for Fusion Energy
2024
Instituto Politécnico de Lisboa
2016-2023
Instituto de Engenharia de Sistemas e Computadores Investigação e Desenvolvimento
2013-2023
Instituto Superior Técnico
2013-2023
Royal Military Academy
2020
Polytechnic Institute of Castelo Branco
2013-2014
TARH (Portugal)
2013
The provision of a particle and power exhaust solution which is compatible with first-wall components edge-plasma conditions key area present-day fusion research mandatory for successful operation ITER DEMO. work package plasma-facing (WP PFC) within the European programme complements laboratory experiments, i.e. in linear plasma devices, electron ion beam loading facilities, studies performed toroidally confined magnetic such as JET, ASDEX Upgrade, WEST etc. connection both groups done via...
Following the first JET ITER-like wall operations a detailed in situ photographic survey of main chamber and divertor was completed. In addition, selection tiles passive diagnostics were removed from vessel made available for post mortem analysis. From results initial analysis, conclusions regarding erosion, deposition, fuel retention material transport during limiter phases have been drawn. The rate deposition on inner outer base remote corners more than an order magnitude less preceding...
Post-mortem studies with ion beam analysis, thermal desorption, and secondary mass spectrometry have been applied for investigating the long-term fuel retention in JET ITER-like wall components. The takes place via implantation co-deposition, highest values were found to correlate thickness of deposited impurity layers. From total amount retained D over half was detected divertor region. majority is on top surface inner divertor, whereas least measured main chamber mid-plane limiter....
Data on erosion and melting of beryllium upper limiter tiles, so-called dump plates (DP), are presented for all three campaigns in the JET tokamak with ITER-like wall. High-resolution images wall show clear signs flash ridge roof-shaped tiles. The melt layers move poloidal direction from inboard to outboard tile, ending last DP tile an upward going waterfall-like structure. Melting was caused mainly by unmitigated plasma disruptions. During ILW campaigns, around 15% 12376 pulses were...
Reliable and accurate knowledge of the physical properties elementary point defects is crucial for predictive modeling evolution radiation damage in materials employed harsh conditions. We have applied positron annihilation spectroscopy to directly detect mono-vacancy created tungsten through particle irradiation at cryogenic temperatures, as well their recovery kinetics. find that efficient self-healing primary takes place Frenkel pair recombination already 35 K, line with an upper bound...
Nuclear fusion is a promising energy source. The International Thermonuclear Experimental Reactor aims to study the feasibility of tokamak-type reactors and test technologies materials for commercial use. One major challenge developing reactor's divertor, which supports high thermal flux. Tungsten was chosen as plasma-facing material, while CuCrZr alloy will be used in cooling pipes. However, gradient between working temperatures these requires use barrier interlayer them. To this end,...
Post mortem analyses of JET ITER-Like-Wall tiles and passive diagnostics have been completed after each the first two campaigns (ILW-1 ILW-2). They show that global fuel inventory is still dominated by co-deposition; hence plasma parameters sputtering processes affecting material migration influence distribution retained fuel. In particular, differences between results from may be attributed to a greater proportion pulses run with strike points in divertor corners, having about 300...
The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013–14 concentrating upper inner divertor, and outer divertor corners, lifetime issues relating to tungsten coatings carbon fibre composite tiles dust/particulate generation. results show that remains region highest deposition in JET-ILW. Variations plasma configurations between first have altered material migration corners divertor. Net is shown be beneficial sense it reduces W...
This paper reports on the first post-mortem analyses of tiles removed from JET after campaigns with ITER-like wall (ILW) during 2011–12 [1]. Tiles divertor have been analysed by ion beam analysis techniques and secondary mass spectrometry to determine amount beryllium deposition deuterium retention in exposed scrape-off layer. Films 10–20 μm thick were present at top tile 1, but only very thin films (< 1 μm) found shadowed areas other tiles. The total Be following ILW campaign was a factor ∼...
Abstract An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T and deuterium-tritium (DT) operations is presented based on most comprehensive ex situ fuel retention data set PFCs from 2015-2016 ILW3 operating period presented. The global 4.19 × 10 23 D atoms, 0.19% injected fuel. inner divertor remains region highest (46.5%). at end calculated as 7.48 22 atoms informative for accountancy, clean-up efficacy waste liability assessments. accumulation rate...
Abstract The Joint European Torus (JET) fusion reactor was upgraded to the metallic wall configuration in 2011 which consisted of bulk beryllium (Be) tiles main chamber and tungsten (W) W-coated CFC divertor (Matthews G.F. et al Phys. Scr. T148 014001). During each campaign, a series damages were observed; on upper dump plates (UDP) positioned top part vessel walls inner wall—mainly affecting guard limiters (IWGL). In both cases, it concluded that causes these unmitigated plasma disruptions....
Post-mortem analyses of individual components provide relevant information on plasma-surface interactions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implantation or co-deposition. Ion Beam techniques are ideal tools for such purposes have been extensively used post-mortem selected from JET following each campaign. In this contribution results removed the ITER-Like Wall (JET-ILW) 2013–2014 campaign presented. The summarize along poloidal...
The JET ITER-Like Wall experiment, with its all-metal plasma-facing components, provides a unique environment for plasma and plasma-wall interaction studies. These studies are of great importance in understanding the underlying phenomena taking place during operation future fusion reactor. Present work summarizes reports fuel retention divertor resulting from two first experimental campaigns Wall. deposition pattern after second campaign shows same trend as was observed campaign: highest...
Post mortem analysis shows that mid and high atomic number metallic impurities are present in deposits on JET plasma facing components with the highest amount of Ni W, therefore largest sink, being found at top inner divertor. Sources defined as "continuous" or "specific", sources arise from ongoing erosion surfaces "specific" linked specific events which decrease over time until they no longer act a source. This contribution evaluates sinks estimates sources, balance gives an indication...